The following report was received from the Kentucky Radiation Health Branch via facsimile:

"A Troxler model 3430 belonging to Gregg Laboratories, Inc, containing a Cs-137 source and a Am-241:Be source was run over by a D6 bull dozer. The company was working at a job site on the campus of Asbury College in Wilmore, KY at the time of the accident. The technician using the gauge was calibrating the gauge on the source block, source rod not exposed, when the dozer ran over the device. The technician set a 50 foot boundary and called the RSO. The RSO called the Wilmore Fire Department (FD) who responded but did not have a survey meter. The Wilmore FD called the Nicholasville, KY FD who then responded. The Nicholasville FD surveyed the damaged gauge with a GM detector and detected radiation but no contamination. Nicholasville FD called CMC Environmental Remediation in Nicholasville, KY who sent a response team to recover the gauge. The gauge was double bagged, put in a 55 gallon drum, surrounded by dirt removed from the site of the accident and everything surveyed by the Nicholasville FD with a Ludlum survey instrument equipped with a GM pancake probe. All survey readings of the site, the dozer, the equipment used to remove the gauge, and surrounding vicinity read background readings of 8 micro-R/hr. Based on [these] findings, [it is] believed that no breach of either source occurred and that there is no radioactive contamination."

The following report was received from the Colorado Department of Public Health and Environment via facsimile:

"The Colorado Department of Public Health and Environment received telephone notification of a lost Iodine-129 sealed source (~24.8 microCuries; Assay date: 6/1/1992) on 8/29/2011 at approximately 4:00 p.m. The University of Colorado, a research licensee, reported that a campus inspection conducted on 8/12/2011 identified a missing gamma counter calibration source. As of 8/29/2011, all efforts to locate the source have failed. It is suspected that the source was discarded with an entire sample rack that was removed from the counter for disposal at some time within the last six months. The source was used for reference in a gamma counter and was an epoxy sealed type source with a small vial geometry.

"The licensee will submit a written report with more detail within the next few days.

"While preparing Loop 2 Main Feed Reg Valve (MFRV) for maintenance, it was placed on its 'air gag' that maintained the MFRV in position, while any small changes in feed flow would be modulated by the associated Bypass Feed Reg Valve (BFRV). Approximately 5 minutes after the MFRV was placed on the air gag, with Steam Generator (S/G) level stable, control room operators observed S/G level start to increase. The operators observed for a short time to see if the associated BFRV would control the level change. When it became apparent that level was not being controlled automatically, the operators took manual control of the BFRV, eventually closing it all the way, and observed that S/G level was then increasing very slowly. While level was still slowly rising, two hi-hi level bistables actuated, generating a P-14 [hi-hi S/G level trip] signal which tripped the main turbine, which then caused an automatic reactor trip. As a result of the reactor trip, all systems functioned as required and there was nothing unusual or not understood."

During the transient, no safeties, primary relief valves or secondary relief valves lifted. All control rods inserted into the core. Auxiliary Feed Water automatically initiated and is supplying the steam generators. Decay heat is being removed via the steam dumps to condenser. The grid is stable with all safety buses powered from offsite power via a normal shutdown electrical lineup. Unit 2 was unaffected by the trip.

"In response to a Notice of Violation (NOV), Global Nuclear Fuels - America (GNFA) committed to perform a review of the existing Integrated Safety Analysis (ISA). An ISA Action Plan and schedule for performing the ISA review was described in GNF-A's response to the NOV and the second milestone (fabrication) was scheduled for completion by July 31, 2011. This milestone was subsequently extended by approximately 30 days. On 8/30/11, GNF-A completed the ISA review for the fabrication area and has identified 125 existing safety controls that are now being designated as Items Relied On For Safety (IROFS). Implementation of the revised safety basis, IROFS and application of management measures to the new IROFS will be completed within 90 days per the ISA Action Plan. Because the revised ISA has designated existing safety controls as additional IROFS, GNF-A is making a report of this completion pursuant to the reporting requirements of 10CFR70 Appendix A(b)(1) within 24 hours."

The NOV inspection report (70-1113/2010-013) was dated June 9, 2010 with an NOV response on July 23, 2010. Milestone #1 was reported in EN #46710 on March 30, 2011. This report concerns milestone #2 of 3.

The licensee will notify the NRC Region 2 Project Manager, the State of North Carolina, and Hanover County.

At 0518 EDT, North Anna Power Station declared an Unusual Event due to seismic activity onsite (EAL HU 1.1). Both units are currently shutdown and electrical power is being supplied from offsite. There were no personnel injuries. There was no radiological release. Site structure and system inspections are in progress. No damage has been identified.

The NRC Resident Inspector and state and local authorities have been notified.